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 Issue dateTitleTopic
CNL-14-038, Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Acc31 March 2014Tennessee Valley Authority'S Seismic Hazard & Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Recommendation 2.1 of Near-Term Task Force Review of Insights from the Fukushima Dai-ichi AccidSafe Shutdown
Boric Acid
Mission time
Safe Shutdown Earthquake
Probabilistic Risk Assessment
Fukushima Dai-Ichi
Seismically rugged
Design basis earthquake
Earthquake
Seismic Walkdown Report
CNL-14-089, (Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)11 December 2014(Bfn), Units 1, 2, and 3 - Application to Modify Technical Specification 2.1.1, Reactor Core Safety Limits (BFN-TS-492)Reactor Vessel Water Level
Stroke time
Anticipated operational occurrence
Minimum Critical Power Ratio
Fuel cladding
Power change
CNL-14-208, Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear Pl17 December 2014Response to NRC Request for Additional Information Regarding the License Amendment Request to Adopt NFPA 805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants for the Browns Ferry Nuclear PlanHot Short
Safe Shutdown
High Radiation Area
Mission time
Fire Barrier
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Coatings
Multiple Spurious Operation
Incorporated by reference
FLEX
Thermoset
Large early release frequency
Severe Accident Management Guideline
Fire Protection Program
Fire Watch
Very Early Warning Fire Detection
CNL-15-056, Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)25 September 2015Application to Modify Technical Specification 2.1.1.2, Reactor Core Minimum Critical Power Ratio Safety Limits (TS-506)Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
MELLLA
CNL-15-085, Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify Technical3 June 2015Response to NRC Request for Additional Information Regarding Proposed Technical Specification Change to Modify Technical Proposed Technical Specification Change to Modify TechnicalStroke time
Fuel cladding
CNL-15-143, the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure Report31 July 2015the Tennessee Valley Authority (TVA) Nuclear Power Group Commercial Grade Dedication Recovery Project - Closure ReportCommercial Grade Dedication
CNL-16-169, Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision28 October 2016Proposed Technical Specifications (TS) Change TS-505 - Request for License Amendments - Extended Power Uprate (EPU) - Supplement 35, Consolidated Power Uprate Safety Analysis Report Revision
CNL-18-112, Extended Power Uprate - Flow Induced Vibration Summary Report13 September 2018Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
CNL-18-134, Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report29 November 2018Extended Power Uprate - Replacement Steam Dryer Revised Analysis and Limit Curves Report
CNL-19-004, Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident Conditions7 June 2019Tennessee Valley Authority, Browns Ferry Nuclear Plant, Unit 2, Completion of Required Action for NRC Order EA-13-109, Reliable Hardened Containment Vents Capable of Operation Under Severe Accident ConditionsFLEX
Design basis earthquake
Spent Fuel Pool Instrumentation
Severe Accident Management Guideline
Hardened vent
CNL-19-032, Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information13 March 2019Proposed Technical Specifications (TS) Change TS-510 - Request for License Amendments - Maximum Extended Load Line Limit Analysis Plus - Supplement 8, Additional Operator Training Information
CNL-19-041, Extended Power Uprate - Unit 1 Flow Induced Vibration Summary Report16 April 2019Extended Power Uprate - Unit 1 Flow Induced Vibration Summary ReportFlow Induced Vibration
Power Uprate
CNL-19-074, Extended Power Uprate - Flow Induced Vibration Summary Report4 September 2019Extended Power Uprate - Flow Induced Vibration Summary ReportFlow Induced Vibration
CNL-20-102, 10 CFR 71.95 Report for 3-60B Casks User16 December 202010 CFR 71.95 Report for 3-60B Casks User
CNL-22-057, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use27 May 2022to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 in Support of Atrium 11 Fuel Use
CNL-22-066, Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional Information18 July 2022Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for in Support of Atrium 11 Fuel Use Supplement 3, Response to Request for Additional InformationStroke time
Anticipated operational occurrence
Abnormal operational transient
CNL-22-100, to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)9 December 2022to Request for License Amendment Regarding Application of Advanced Framatome Methodologies, and Adoption of TSTF-564 Revision 2 for Browns Ferry Nuclear Plant Units 1, 2, and 3,in Support of Atrium 11 Fuel Use at Browns Ferry (TS-535)Safety Limit Minimum Critical Power Ratio
Anticipated operational occurrence
Abnormal operational transient
Feedwater Controller Failure
MELLLA
ML02304033819 September 2002Part 2 of 4 - Course Outline for R-304-B and BWR Systems Lesson PlansReactor Vessel Water Level
Loop seal
Hydrostatic
Earthquake
Fuel cladding
Power change
Coast down
ML02304036119 September 2002Part 4 of 4 - Course Outline for R-304-B and BWR Systems Lesson Plans
ML0234703085 December 2002Steam Generator Inservice Inspection, Steam Generator Tube Plugging & Repair 30-Day ReportEddy Current Testing
ML03065071625 February 2003Special Report Per Technical Specification 5.6.6., Problem Investigation Process No.: 0-03-0154, 0-03-0415Post Accident Monitoring
ML03254037231 May 2003Pressure-Temperature Curves for TVA Browns Ferry Units 2 and 3Shutdown Margin
Anticipated operational occurrence
Hydrostatic
Finite Element Analysis
ML03273155729 September 2003Technical Letter Report on the Third 10-Year Interval Inservice Inspection Request for Relief Nos. 02-004 and 02-005 for Oconee Nuclear Station, Unit 1Hydrostatic
VT-2
Incorporated by reference
Dissimilar Metal Weld
ML04121026131 January 2003Tennessee Valley Authority Systems and Analysis Browns Ferry Nuclear Plant Probabilistic Safety Assessment Unit 2 Summary, Revision 1Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
ML04155078629 February 2004FRA-ANP Document No. 77-5038568-00, LBB Evaluation of the Core Flood and Low Pressure Injection/Decay Heat Removal Piping Systems for Oconee Unit 3.Safe Shutdown Earthquake
Finite Element Analysis
Stress corrosion cracking
License Renewal
Pressure Boundary Leakage
Pressure boundary leak
Unidentified leakage
ML04184011430 April 2004Engineering Report GE-NE-0000-0023-1250-1, Rev 0, Browns Ferry, Units 1, 2 and 3, Steam Dryer Analysis for Extended Power Uprate Conditions.Safe Shutdown
Safe Shutdown Earthquake
Operating Basis Earthquake
Finite Element Analysis
Earthquake
Flow Induced Vibration
ML04184011630 June 2004Proposed Technical Specifications Change TS-431, Extended Power Uprate UFSAR Review Matrix, Enclosure 6Safe Shutdown
Shutdown Margin
Reactor Vessel Water Level
Safety Limit Minimum Critical Power Ratio
Ultimate heat sink
Non-Destructive Examination
Stroke time
Anticipated operational occurrence
Time to boil
Internal Flooding
Hydrostatic
Probabilistic Risk Assessment
Coatings
Nondestructive Examination
Temporary Modification
Finite Element Analysis
Significance Determination Process
Feedwater Controller Failure
Large early release frequency
MELLLA
Turbine Missile
Fuel cladding
Fire Protection Program
Flow Induced Vibration
GOTHIC
Power Uprate
Failure to Scram
ML04184041330 April 2004Engineering Report, Steam Dryer Analysis for Extended Power Uprate ConditionsSafe Shutdown
Safe Shutdown Earthquake
Operating Basis Earthquake
Finite Element Analysis
Earthquake
Flow Induced Vibration
ML0420803362 July 2004Response to Request for Additional Information Related to Technical Specifications Change No. TS-405 Alternative Source TermSafe Shutdown
Ultimate heat sink
Grab sample
Design basis earthquake
Earthquake
ML04238024331 August 2003Tennessee Valley Authority System and Analysis Browns Ferry Nuclear Plant, Probabilistic Safety Assessment, Certification and Per ResolutionSafe Shutdown
Mission time
Finite Element Analysis
Large early release frequency
Hardened vent
ML04280005227 May 2004Zebra Mussels: Biology, Impacts, and Control, Chapter 13Zebra Mussel
ML04296039115 October 2004ORNL/NRC/LTR-04/18, Electronic Archival of the Results of Pressurized Thermal Shock Analyses for Beaver Valley, Oconee, and Palisades Reactor Pressure Vessels Generated with the 04.1 Version of Favor.
ML04338032115 November 2004American Society of Mechanical Engineers Section XI, in Service Inspection ProgramProbabilistic Risk Assessment
Finite Element Analysis
Aging Management
EVT-1
ML04355027131 March 2004CTRS-Report, Thermal - Hydraulic Uncertainty Analysis in Pressurized Thermal Shock Risk Assessment.Loop seal
Probabilistic Risk Assessment
Earthquake
ML0505600378 February 200512-5023272-01, Risk Assessment for Alternate STS End States.Safe Shutdown
Boric Acid
Shutdown Margin
Ultimate heat sink
Mission time
Time to boil
Probabilistic Risk Assessment
Offsite Circuit
Manual Operator Action
ML05077037011 March 2005Technical Specifications (TS) Change TS-447, Request for Additional Information (RAI) - Extension of Channel Calibration Surveillance Requirement Performance Frequency and Allowable Value RevisionSafe Shutdown Earthquake
ML05136015512 August 1994IPE-PRA Revision 1, Unit 2.
ML05136016213 April 1995IPE-PRA Revision 1A, Unit 2.
ML05164030722 July 2005Third 10-Year Interval Inservice Inspection Program Plan Requests for Relief 04-ON-002 and 04-ON-003Incorporated by reference
Liquid penetrant
Dissimilar Metal Weld
Scaffolding
ML0603806712 February 2006Response to NRC Request for Additional Information Regarding Individual Plant Examination of External Events (IPEEE) for Severe Accident Vulnerabilities - Submittal of Browns Ferry Unit 1 Seismic and Internal Fires IPEEE ReportsHot Short
Safe Shutdown
High winds
Ultimate heat sink
Probabilistic Risk Assessment
Aging Management
Significance Determination Process
Design basis earthquake
License Renewal
Earthquake
ML06062054827 February 2006Brown Ferry Nuclear EPU Containment Overpressure (COP) Credit Risk Assessment.
ML06072027330 November 1992a Guide for Environmental and Best Management Practices for Tennessee Valley Authority Transmission Construction and Maintenance Activities
ML06072029328 February 2005Hydrothermal Modeling of Browns Ferry Nuclear Plant with Units 1, 2, and 3 at Extended Power UprateUltimate heat sink
ML06072035431 March 2006GE-NE-0000-0049-6652-01NP, Rev 0, General Electric Boiling Water Reactor Steam Dryer Scale Model Test Based Fluctuating Load Definition Methodology, March 2006 Benchmark ReportFinite Element Analysis
Flow Induced Vibration
ML06088046421 March 2006BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 1High winds
Mission time
Internal Flooding
Probabilistic Risk Assessment
Coatings
Large early release frequency
ML06107063230 April 2006Units 1, 2, & 3 - GENE-0000-0052-3661-01-NP, Test Report #1, Browns Ferry Nuclear Plant; Unit 1, Scale Model Test.
ML06130044131 May 2006C.D.I. Report 06-11, Rev 1, Hydrodynamic Loads on Browns Ferry, Unit 1 Steam Dryer to 200 Hz.
ML06130044331 May 2006GE-NE-0000-0053-7413-R0-NP, Browns Ferry, Units 1, 2 & 3 Steam Dryer Stress, Dynamic and Fatigue Analyses for EPU Conditions.Finite Element Analysis
Earthquake
Flow Induced Vibration
ML06209048210 July 2006BFN EPU Containment Overpressure (COP) Credit Risk Assessment, Rev. 2High winds
Mission time
Internal Flooding
Probabilistic Risk Assessment
Large early release frequency
ML06213034331 July 2006C.D.I. Report No. 06-11, Revision 2, Hydrodynamic Loads on Browns Ferry Nuclear Unit 1 Steam Dryer to 200 Hz.